[en] In-pile functional tests of breeding blankets have been planned by Japan Atomic Energy Agency (JAEA), using a test blanket module (TBM) which will be loaded in the International Thermonuclear Experimental Reactor (ITER). In preparation for the in-pile functional tests, JAEA has been performing irradiation experiments of lithium titanate (Li₂TiO₃), which is the first candidate of solid breeder materials for the blanket of the demonstration reactor (DEMO) under designing in Japan. The present report describes 1) results of a detailed design and trial fabrication tests of a dismantling apparatus for irradiation capsules which were used in irradiation experiments by the Japan Materials Testing Reactor (JMTR) of JAEA, and 2) results of a preliminary investigation of a glove box facility for post-irradiation examinations (PIEs). In the detailed design of the dismantling apparatus, detailed specifications and the installation methods were examined, based on results of a conceptual design and basic design which were carried out before the present work. In the trial fabrication, cutting tests were curried out by making a mockup of a cutting component, which is a key component of the dismantling apparatus, as well as some simulated JMTR irradiation capsules. Good cutting performance was attained by optimizing the cutting speed, through repeated reviews of the results of the trial fabrication tests. In addition, improvement of the capsule clamping mechanism brought a prospect for feasibility of the apparatus in terms of operational convenience such as setting and removal, respectively, of the capsule before and after the cutting. Furthermore, a preliminary investigation of a glove box facility was carried out in order to secure a facility for PIE work after the capsule dismantling, which revealed a technical feasibility. (author)